Zirconium alloy fuel cladding

Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component

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376414, 376457, G21C 300

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active

054369479

ABSTRACT:
A cladding is provided for use in housing fissionable material in water cooled nuclear fission reactors. The cladding has inner and outer surfaces and includes (1) a cross-section of a Zirconium-based alloyed matrix, and (2) alloying elements in sufficient concentration to form precipitates disposed in the matrix. The cladding includes no more than 20 parts per million nitrogen by weight and is typically a modified Zircaloy-2 or Zircaloy-4. Metallurgically bonded to the inner region of the cladding is a zirconium barrier layer.

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Armand, M.; Demars, J. P. Givord; and Trolliet, G., "Influence of the Structure and the Interstitial Impurities on the Corrosion of Zircaloy-2 by Water and Steam", Journal of the Electrochemical Socity, vol. 4, pp. 104-108, 1966.
Kass, S.; Grozier, J. D.; and Shubert, F. L., "Effects of Silicon, Nitrogen and Oxygen on the Corrosion and Hydrogen Absorption of Zircaloy-2", Corrosion (NACE) vol. 20 pp. 350t-360, 1964.
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